Module;Purpose;"Initial data";"Assumptions / functional"
NUDAPS;"Calculation of one-group neutron cross-sections, various functionals, which are linear combinations, products and ratios of one-group neutron cross-sections and their uncertainties";"Evaluated neutron data and covariance matrices, neutron spectrum (these data are placed in a specialised database of evaluated neutron data of actinide nuclei)";"The module contains a set of evaluated neutron data and covariance matrices for the main actinide nuclei in the GENDF and BOXER formats (for covariance matrices), a set of standardized neutron spectra (fission, Maxwell, Fermi, etc.) and neutron spectra characteristic of various types of power reactors (the spectra can be specified in both analytical and tabular forms)."
NUCLEX;"Calculation of nuclide composition evolution (mass and concentration), activity, radiotoxicity, heat release, neutron and gamma sources of nuclear fuel";"Initial isotopic composition of the fuel, one-group neutron fluxes and neutron cross-sections, both determined at various stages of fuel irradiation in the reactor and one-group flux and cross-sections averaged over the entire irradiation cycle and constant in time, specific power density, nuclear fuel burnup";"Basic set of actinide nuclei: 234U, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 242mAm, 243Am, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm, 247Cm, 248Cm. Basic set of fission and activation products: 3H, 14C, 36Cl, 54Mn, 55Fe, 60Co, 59Ni, 63Ni, 79Se, 85Kr, 87Rb, 90Sr, 93Mo, 94Nb, 93Zr, 98Tc,99Tc, 102Rh, 106Ru, 107Pd, 110mAg, 113mCd, 121mSn, 125Sb, 126Sn, 125mTe, 127mTe, 126Sn, 129I, 134Cs, 135Cs, 137Cs, 144Ce, 146Pm, 147Pm, 146Sm,147Sm, 151Sm, 152Eu, 154Eu, 155Eu, 166mHo. Output data (masses and concentrations of the main actinides, fission products, radioactivity, decay heat, radiotoxicity, neutron and gamma radiation) are given for the end of the irradiation cycle, after cooling, for the 100th, 1000th and 10000th years. The functionality for estimating the nuclear data and technological uncertainty of the design characteristics is implemented."
NUCAB;"Calculation of the values and uncertainties of the corrections for the nuclear fuel enrichment and the total neutron flux, taking into account the conservation of the fraction of heavy nuclei in the fuel, reactivity and power of the reactor plant";"Fuel isotope composition (design and actual), one-group neutron cross-sections, covariance matrices and neutron flux";"Various methods for estimating the enrichment and total neutron flux corrections and their uncertainties are implemented in order to select the most appropriate method for its subsequent implementation. The uncertainties of the corrections associated with the initial neutron data are estimated."
FANES;"Calculation of material flows and needs for NFC goods and services for the main stages of the NFC front-end and back-end, assessment of uncertainties in material indicators";"Dynamics of commissioning and decommissioning of power units, parameters of fuel use and SNF/RW production, isotope composition of fresh and spent fuel, characteristics of the strategy for handling SNF/RW, fissile materials, principles of prioritisation/management of stocks and reserves of nuclear materials";"It is possible to take into account the radioactive decay of nuclides in external part of the NFC when they appear in the NFC in different time periods, simulate delays at various stages of the NFC and in SNF storage facilities, set priorities for the consumption of limited resources and the utilisation of limited capacities of NFC facilities, evaluate the uncertainty in the material indicators caused by the uncertainty in the initial technical data."
ECNES;"Calculation for the NES development scenario of the total discounted costs, net present value, internal rate of return, profitability index, payback period, levelised unit energy cost (LUEC), assessment of the uncertainties in economic indicators due to the uncertainty of the initial cost data";"Dynamics of commissioning and decommissioning of power units, technical and economic parameters of power units, material flows and needs for NFC goods and services (needs for natural uranium, uranium conversion and enrichment services, fresh fuel fabrication, SNF storage and processing, etc.), cost data on construction, operation and decommissioning of power units, NFC goods and services, discount rate, electricity tariff";"It is possible to consider different distributions of capital costs (uniform, sinusoidal distribution, distribution of a second degree polynomial, arbitrary distribution), adjust capital costs for units that remain in operation beyond the forecast horizon, and account for depreciation deductions during the operation of historical capacities. It is also possible to evaluate the uncertainty of economic indicators caused by the uncertainty of the initial cost data (uniform and triangular distribution of costs, correlated and uncorrelated distributions of input values)."